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Proposed Tech Specs,Changing Period of Time That Portable gamma-sensitive Ion Chamber Utilized as Temporary Substitute,Provided That Substitute Can Be Monitored by Reactor OperatorML20199J615 |
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Dow Chemical Company |
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Issue date: |
01/29/1998 |
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DOW CHEMICAL CO. |
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Shared Package |
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ML20199J606 |
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References |
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NUDOCS 9802050362 |
Download: ML20199J615 (1) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20199J6151998-01-29029 January 1998 Proposed Tech Specs,Changing Period of Time That Portable gamma-sensitive Ion Chamber Utilized as Temporary Substitute,Provided That Substitute Can Be Monitored by Reactor Operator ML20087E4231995-08-0707 August 1995 Proposed Tech Specs Re Technical Support for Individual ML20078M1451995-02-0808 February 1995 Proposed Tech Specs Re Proposed Amend to License R-108 ML20029E4831994-05-31031 May 1994 Proposed Tech Specs,Adding Definition of Surveillance Interval,Changing Language Intended to Clarify Some Points & Bring Other Up to Date,Changing Spec Re Min Period Setpoint & Spec for Exam of Fuel Elements ML20065H2041990-10-15015 October 1990 Proposed Tech Specs Re Installation of Microprocessor & Control Sys ML20154C2761988-04-30030 April 1988 Mods Supplementing Tech Specs for Renewal of License R-108 ML20214T0881987-03-31031 March 1987 Tech Specs for Dow Triga Research Reactor,Facility License R-108 ML20214C5751986-12-31031 December 1986 Proposed Tech Specs for Dow Triga Research Reactor ML18026A9341984-04-0303 April 1984 Proposed Amend to Tech Specs,Changing Physical Security Plan Description 1998-01-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20199J6151998-01-29029 January 1998 Proposed Tech Specs,Changing Period of Time That Portable gamma-sensitive Ion Chamber Utilized as Temporary Substitute,Provided That Substitute Can Be Monitored by Reactor Operator ML20087E4231995-08-0707 August 1995 Proposed Tech Specs Re Technical Support for Individual ML20078M1451995-02-0808 February 1995 Proposed Tech Specs Re Proposed Amend to License R-108 ML20029E4831994-05-31031 May 1994 Proposed Tech Specs,Adding Definition of Surveillance Interval,Changing Language Intended to Clarify Some Points & Bring Other Up to Date,Changing Spec Re Min Period Setpoint & Spec for Exam of Fuel Elements ML20065H2041990-10-15015 October 1990 Proposed Tech Specs Re Installation of Microprocessor & Control Sys ML20154C2761988-04-30030 April 1988 Mods Supplementing Tech Specs for Renewal of License R-108 ML20214T0761987-04-20020 April 1987 Dow Triga Research Reactor Requalification Program ML20214T0881987-03-31031 March 1987 Tech Specs for Dow Triga Research Reactor,Facility License R-108 ML20214C5751986-12-31031 December 1986 Proposed Tech Specs for Dow Triga Research Reactor ML18026A9341984-04-0303 April 1984 Proposed Amend to Tech Specs,Changing Physical Security Plan Description 1998-01-29
[Table view] |
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Applicability These specifications apply to the radiation monitoring information available to the reactor operator during operation of the reactor.
Obiectiu The objective of these specifications is to ensure that the reactor operator has adequate information to assure safe operation of the reactor.
Snecifications A Continuous Air Monitor (CAM)(with readout meter and audible alarm) to measure radioactive particulates in the reactor room must be operating during operation of the reactor.
The Area Monitor (AM)(with readota meter and audible alarm)in the reactor room must be operating during operation of the reactor or when work is being done on or around the reactor core or experimental facilities. During short periods of repair to this monitor, not to exceed sixty days, reactor operations or work on or around the core or experimental facilities may continue while a portable gamma-sensitive ion chamber is utilized as a temporary substitute, provided that the substitute can be monitored by the reactor operator.
Bases The radiation monitors provide information of existing levels of radiation and air-bome radioactive materials which could endanger operating personnel or which could warn of possible malfunctions of the reactor or the experiments in the reactor.
Anwndmen;Na 8 9802050362 980129 n-PDR ADOCK 05000264 V PDR
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